Text

License and Technical Specifications, Amendment 144 and 144, Changes to TS to Allow Use of Westinghouse-developed/NRC-approved Analytical Methods Used to Establish COLs
	ML080510083
Person / Time
Site:	Comanche Peak
Issue date:	04/02/2008
From:	; NRC/NRR/ADRO/DORL/LPLIV
To:	;
	Singal, Balwant, 415-3016, NRR/DORL/LPL4
Shared Package
ML080500666	List: ML080500627; ML080510083;
References
	TAC MD5243, TAC MD5244, TAC MD6212, TAC MD6213
	Download: ML080510083 (41)
	v • d • e

(3)

Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4)

Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)

Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)

Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission=s regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level Luminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal in accordance with the conditions specified herein.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Unit 1 Amendment No.

144 144 (3)

Luminant Generation Company LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4)

Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)

Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)

Luminant Generation Company LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission=s regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level Luminant Generation Company LLC is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal in accordance with the conditions specified herein.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. Luminant Generation Company LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Antitrust Conditions DELETED Unit 2 Amendment No.

144 144

COMANCHE PEAK - UNITS 1 AND 2 i

Amendment No. 64 TABLE OF CONTENTS 1.0 USE AND APPLICATION............................................................................................ 1.1-1 1.1 Definitions............................................................................................................. 1.1-1 1.2 Logical Connectors............................................................................................... 1.2-1 1.3 Completion Times................................................................................................ 1.3-1 1.4 Frequency............................................................................................................ 1.4-1 2.0 SAFETY LIMITS (SLs)................................................................................................. 2.0-1 2.1 SLs......................................................................................................................2.0-1 2.2 SL Violations........................................................................................................ 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY........................... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.......................................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS.................................................................... 3.1-1 3.1.1 SHUTDOWN MARGIN (SDM)...................................................................... 3.1-1 3.1.2 Core Reactivity.............................................................................................. 3.1-2 3.1.3 Moderator Temperature Coefficient (MTC)................................................... 3.1-4 3.1.4 Rod Group Alignment Limits......................................................................... 3.1-7 3.1.5 Shutdown Bank Insertion Limits.................................................................... 3.1-11 3.1.6 Control Bank Insertion Limits........................................................................ 3.1-13 3.1.7 Rod Position Indication................................................................................. 3.1-16 3.1.8 PHYSICS TESTS Exceptions - MODE 2....................................................... 3.1-19 3.2 POWER DISTRIBUTION LIMITS......................................................................... 3.2-1 3.2.1 Heat Flux Hot Channel Factor (F (Z))........................................................... 3.2-1 Q

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F

)........................................ 3.2-N H

11 3.2.3 AXIAL FLUX DIFFERENCE (AFD)............................................................... 3.2-14 3.2.4 QUADRANT POWER TILT RATIO (QPTR).................................................. 3.2-18 3.3 INSTRUMENTATION........................................................................................... 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation................................................. 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation..... 3.3-21 3.3.3 Post Accident Monitoring (PAM) Instrumentation......................................... 3.3-35 3.3.4 Remote Shutdown System............................................................................ 3.3-40 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation............. 3.3-43 3.3.6 Containment Ventilation Isolation Instrumentation........................................ 3.3-48 3.3.7 Control Room Emergency Filtration System (CREFS)

Actuation Instrumentation............................................................................. 3.3-52 (continued)

, 144

TABLE OF CONTENTS (continued)

COMANCHE PEAK - UNITS 1 AND 2 iv Amendment No. 64 3.9 REFUELING OPERATIONS................................................................................ 3.9-1 3.9.1 Boron Concentration..................................................................................... 3.9-1 3.9.2 Unborated Water Source Isolation Valves.................................................... 3.9-3 3.9.3 Nuclear Instrumentation................................................................................ 3.9-5 3.9.4 Containment Penetrations............................................................................ 3.9-7 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation -

High Water Level.......................................................................................... 3.9-9 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation -

Low Water Level........................................................................................... 3.9-11 3.9.7 Refueling Cavity Water Level........................................................................ 3.9-13 4.0 DESIGN FEATURES................................................................................................... 4.0-1 4.1 Site Location........................................................................................................ 4.0-1 4.2 Reactor Core........................................................................................................ 4.0-1 4.3 Fuel Storage......................................................................................................... 4.0-2 5.0 ADMINISTRATIVE CONTROLS.................................................................................. 5.0-1 5.1 Responsibility....................................................................................................... 5.0-1 5.2 Organization......................................................................................................... 5.0-2 5.3 Unit Staff Qualifications........................................................................................ 5.0-5 5.4 Procedures........................................................................................................... 5.0-6 5.5 Programs and Manuals........................................................................................ 5.0-7 5.6 Reporting Requirements...................................................................................... 5.0-29 5.7 High Radiation Area............................................................................................. 5.0-40

, 144

Rod Position Indication 3.1.7 COMANCHE PEAK - UNITS 1 AND 2 3.1-16 Amendment No. 64 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Digital Rod Position Indication (DRPI) System and the Demand Position Indication System shall be OPERABLE APPLICABILITY:

MODES 1 and 2.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each inoperable rod position indicator and each demand position indicator per bank.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One DRPI per group inoperable for one or more groups.

A.1 Verify the position of the rods with inoperable position indicators indirectly by using core power distribution measurement information.

OR A.2 Reduce THERMAL POWER to d 50% RTP.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 hours (continued)

, 144

Rod Position Indication 3.1.7 ACTIONS (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.1-17 Amendment No. 64 CONDITION REQUIRED ACTION COMPLETION TIME B. More than one DRPI per group inoperable.

B.1 Place the control rods under manual control.

AND B.2 Monitor and record RCS Tavg.

AND B.3 Verify the position of the rods with inoperable position indicators indirectly by using core power distribution measurement information.

AND B.4 Restore inoperable position indicators to OPERABLE status such that a maximum of one DRPI per group is inoperable.

Immediately Once per 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 24 hours C.

One or more rods with inoperable DRPIs have been moved in excess of 24 steps in one direction since the last determination of the rod's position.

C.1 Verify the position of the rods with inoperable position indicators indirectly by using core power distribution measurement information.

OR C.2 Reduce THERMAL POWER to 50% RTP.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 8 hours (continued)

, 144

FQ(Z) (CAOC-W(Z) Methodology) 3.2.1.1 COMANCHE PEAK - UNITS 1 AND 2 3.2-1 Amendment No. 64 3.2 POWER DISTRIBUTION LIMITS

, 144 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

3.2.1.1 Heat Flux Hot Channel Factor (FQ(Z)) (CAOC-W(Z) Methodology)

LCO 3.2.1.1 FQ(Z), as approximated by FQ C(Z) and FQ W(Z), shall be within the limits specified in the COLR.

NOTE----------------------------------------------

This LCO is only applicable to Unit 1, Cycle 13.

APPLICABILITY:

MODE 1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. FQ C(Z) not within limit.

15 minutes after each FQ C(Z) determination A.1 Reduce THERMAL POWER 1% RTP for each 1% FQ C(Z ) exceeds limit.

AND A.2 Reduce Power Range Neutron Flux -- High trip setpoints 1% for each 1% FQ C(Z) exceeds limit.

AND A.3 Reduce Overpower N-16 trip setpoints 1% for each 1% FQ C(Z) exceeds limit.

AND A.4 Perform SR 3.2.1.1.1.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each FQ C(Z) determination 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each FQ C(Z) determination Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued)

FQ(Z) (CAOC-W(Z) Methodology) 3.2.1.1 ACTIONS (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.2-2 Amendment No. 64, 144 CONDITION REQUIRED ACTION COMPLETION TIME B. FQ W(Z) not within limits.

B.1 Reduce AFD limits 1%

for each 1% FQ W(Z) exceeds limit.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. Required Action and associated Completion Time not met.

C.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

FQ(Z) (CAOC-W(Z) Methodology) 3.2.1.1 COMANCHE PEAK - UNITS 1 AND 2 3.2-3 Amendment No. 64 SURVEILLANCE REQUIREMENTS

NOTE------------------------------------------------------------

During power escalation following shutdown, THERMAL POWER may be increased until an equilibrium power level has been achieved at which a power distribution map is obtained.

SURVEILLANCE FREQUENCY SR 3.2.1.1.1 Verify FQ C(Z) is within limit.

Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions after exceeding, by 20% RTP, the THERMAL POWER at which FQ C(Z) was last verified AND

, 144 31 EFPD thereafter (continued)

FQ(Z) (CAOC-W(Z) Methodology) 3.2.1.1 SURVEILLANCE REQUIREMENTS (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.2-4 Amendment No. 64 SURVEILLANCE FREQUENCY SR 3.2.1.1.2 -------------------------------NOTE-----------------------------------

If FQ C(Z) measurements indicate maximum over z

>>

1/4

º

¬

Z K

Z FC Q

has increased since the previous evaluation of FQ C(Z):

a. Increase FQ W(Z) by the appropriate factor and reverify FQ W(Z) is within limits; or

b. Repeat SR 3.2.1.1.2 once per 7 EFPD until two successive flux maps indicate maximum over z

>>

1/4

º

¬

Z K

Z FC Q

has not increased.

Verify FQ W(Z) is within limit.

Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND (continued)

, 144

FQ(Z) (CAOC-W(Z) Methodology) 3.2.1.1 COMANCHE PEAK - UNITS 1 AND 2 3.2-5 Amendment No. 64 SURVEILLANCE FREQUENCY SR 3.2.1.1.2 (continued)

Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions after exceeding, by 20% RTP, the THERMAL POWER at which FQ c(Z) was last verified

, 144 AND 31 EFPD thereafter

FQ(Z) (RAOC-W(Z) Methodology) 3.2.1.2 COMANCHE PEAK - UNITS 1 AND 2 3.2-6 Amendment No. 144 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

3.2.1.2 Heat Flux Hot Channel Factor (FQ(Z)) (RAOC-W(Z) Methodology)

LCO 3.2.1.2 FQ (Z), as approximated by FQ C(Z) and FQ W(Z), shall be within the limits specified in the COLR.

NOTE----------------------------------------------

This LCO is not applicable to Unit 1, Cycle 13.

APPLICABILITY:

MODE 1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

NOTE----------------

Required Action A.4 shall be completed whenever this Condition is entered.

A. FQ C(Z) not within limit.

A.1 Reduce THERMAL POWER 1% RTP for each 1% FQ C(Z ) exceeds limit.

AND A.2 Reduce Power Range Neutron Flux -- High trip setpoints 1% for each 1% FQ C(Z) exceeds limit.

AND A.3 Reduce Overpower N-16 trip setpoints 1% for each 1% FQ C(Z) exceeds limit.

AND A.4 Perform SR 3.2.1.2.1 and SR 3.2.1.2.2.

15 minutes after each FQ C(Z) determination 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each FQ C(Z) determination 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each FQ C(Z) determination Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued)

FQ(Z) (RAOC-W(Z) Methodology) 3.2.1.2 ACTIONS (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.2-7 Amendment No. 144 CONDITION REQUIRED ACTION COMPLETION TIME

NOTE----------------

Required Action B.4 shall be completed whenever this Condition is entered.

B. FQ W(Z) not within limits.

B.1 Reduce AFD limits 1%

for each 1% FQ W(Z) exceeds limit.

AND B.2 Reduce Power Range Neutron Flux - High trip setpoints > 1% for each 1% that the maximum allowable power of the AFD limits is reduced.

AND B.3 Reduce Overpower N-16 trip setpoints > 1% for each 1% that the maximum allowable power of the AFD limits is reduced.

AND B.4 Perform SR 3.2.1.2.1 and SR 3.2.1.2.2.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 72 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Prior to increasing THERMAL POWER above the maximum allowable power of the AFD limits.

C. Required Action and associated Completion Time not met.

C.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

FQ(Z) (RAOC-W(Z) Methodology) 3.2.1.2 COMANCHE PEAK - UNITS 1 AND 2 3.2-8 Amendment No. 144 SURVEILLANCE REQUIREMENTS

NOTE------------------------------------------------------------

During power escalation following shutdown, THERMAL POWER may be increased until an equilibrium power level has been achieved at which a power distribution measurement is obtained.

SURVEILLANCE FREQUENCY SR 3.2.1.2.1 Verify FQ C(Z) is within limit.

Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions after exceeding, by 20% RTP, the THERMAL POWER at which FQ C(Z) was last verified AND 31 EFPD thereafter (continued)

FQ(Z) (RAOC-W(Z) Methodology) 3.2.1.2 SURVEILLANCE REQUIREMENTS (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.2-9 Amendment No. 144 SURVEILLANCE FREQUENCY SR 3.2.1.2.2 -------------------------------NOTE-----------------------------------

If FQ C(Z) measurements indicate maximum over z

>>

1/4

º

¬

Z K

Z FC Q

has increased since the previous evaluation of FQ C(Z):

a. Increase FQ W(Z) by an appropriate factor specified in the COLR and reverify FQ W(Z) is within limits; or

b. Repeat SR 3.2.1.2.2 once per 7 EFPD until either a.

above is met or two successive power distribution measurements indicate maximum over z

>>

1/4

º

¬

Z K

Z FC Q

has not increased.

Verify FQ W(Z) is within limit.

Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND (continued)

FQ(Z) (RAOC-W(Z) Methodology) 3.2.1.2 SURVEILLANCE REQUIREMENTS (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.2-10 Amendment No. 144 SURVEILLANCE FREQUENCY SR 3.2.1.2.2 (continued)

Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions after exceeding, by 20% RTP, the THERMAL POWER at which FQ C(Z) was last verified AND 31 EFPD thereafter

FN

'H 3.2.2 COMANCHE PEAK - UNITS 1 AND 2 3.2-11 Amendment No. 66, 144 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F N'H )

LCO 3.2.2 FN'H shall be within the limits specified in the COLR.

APPLICABILITY:

MODE 1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------NOTE--------------

Required Actions A.2 and A.3 must be completed whenever Condition A is entered.

FN'H not within limit.

A.1.1 Restore FN'H to within limit.

OR A.1.2.1 Reduce THERMAL POWER to < 50% RTP.

AND A.1.2.2 Reduce Power Range Neutron Flux - High trip setpoints to 55% RTP.

AND A.2 Perform SR 3.2.2.1.

AND 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 4 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 24 hours (continued)

FN°H 3.2.2 ACTIONS (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.2-12 Amendment No. 64, 144 CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.3

NOTE-------------

THERMAL POWER does not have to be reduced to comply with this Required Action.

Perform SR 3.2.2.1.

Prior to THERMAL POWER exceeding 50% RTP AND Prior to THERMAL POWER exceeding 75% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER reaching 95% RTP B. Required Action and associated Completion Time not met.

B.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

FN

'H 3.2.2 SURVEILLANCE REQUIREMENTS COMANCHE PEAK - UNITS 1 AND 2 3.2-13 Amendment No. 64

NOTE-------------------------------------------------------------

During power escalation following shutdown, THERMAL POWER may be increased until an equilibrium power level has been achieved at which a power distribution measurement is obtained.

SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify FN'H is within limits specified in the COLR.

Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND 31 EFPD thereafter

, 144

AFD (CAOC METHODOLOGY) 3.2.3.1 COMANCHE PEAK - UNITS 1 AND 2 3.2-14 Amendment No. 64 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.2.3.1 AXIAL FLUX DIFFERENCE (AFD) (Constant Axial Offset Control (CAOC) Methodology)

LCO 3.2.3.1 The AFD:

a.

Shall be maintained within the target band about the target flux difference. The target band is specified in the COLR.

b.

May deviate outside the target band with THERMAL POWER

< 90% RTP but 50% RTP, provided AFD is within the acceptable operation limits and cumulative penalty deviation time is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The acceptable operation limits are specified in the COLR.

c.

May deviate outside the target band with THERMAL POWER

< 50% RTP.

NOTES---------------------------------------------

1.

The AFD shall be considered outside the target band when two or more OPERABLE excore channels indicate AFD to be outside the target band.

2.

With THERMAL POWER t 50% RTP, penalty deviation time shall be accumulated on the basis of a 1 minute penalty deviation for each 1 minute of power operation with AFD outside the target band.

3.

With THERMAL POWER < 50% RTP, penalty deviation time shall be accumulated on the basis of a 0.5 minute penalty deviation for each 1 minute of power operation with AFD outside the target band.

4.

A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months of operation may be accumulated with AFD outside the target band without penalty deviation time during surveillance of power range channels in accordance with SR 3.3.1.6, provided AFD is maintained within acceptable operation limits.

5.

This LCO is only applicable to Unit 1, Cycle 13.

APPLICABILITY:

MODE 1 with THERMAL POWER > 15% RTP

, 144

AFD (CAOC METHODOLOGY) 3.2.3.1 COMANCHE PEAK - UNITS 1 AND 2 3.2-15 Amendment No. 64, 144 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. THERMAL POWER 90% RTP.

AND AFD not within the target band.

A.1 Restore AFD to within target band.

15 minutes B. Required Action and associated Completion Time of Condition A not met.

B.1 Reduce THERMAL POWER to < 90% RTP.

15 minutes C. -------------NOTE---------------

Required Action C.1 must be completed whenever Condition C is entered.

THERMAL POWER < 90%

and 50% RTP with cumulative penalty deviation time > 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

OR THERMAL POWER < 90%

and 50% RTP with AFD not within the acceptable operation limits.

C.1 Reduce THERMAL POWER to < 50% RTP.

30 minutes (continued)

AFD (CAOC METHODOLOGY) 3.2.3.1 COMANCHE PEAK - UNITS 1 AND 2 3.2-16 Amendment No. 64, 144 CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time for Condition C not met.

D.1 Reduce THERMAL POWER to < 15% RTP.

9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1.1 Verify AFD is within limits for each OPERABLE excore channel.

7 days SR 3.2.3.1.2 Not Used.

SR 3.2.3.1.3 -------------------------------NOTE-----------------------------------

The initial target flux difference after each refueling may be determined from design predictions.

Determine, by measurement, the target flux difference of each OPERABLE excore channel.

Whenever FQ W(Z) is verified per 3.2.1.1.2.

AFD (RAOC METHODOLOGY) 3.2.3.2 COMANCHE PEAK - UNITS 1 AND 2 3.2-17 Amendment No. 144 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.2.3.2 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC)

Methodology)

LCO 3.2.3.2 The AFD in % flux difference units shall be maintained within the limits specified in the COLR.

NOTE-------------------------------------------------

1.

The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

2.

This LCO is not applicable to Unit 1, Cycle 13.

APPLICABILITY:

MODE 1 with THERMAL POWER > 50% RTP ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits.

A.1 Reduce THERMAL POWER to < 50% RTP.

30 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.2.1 Verify AFD is within limits for each OPERABLE excore channel.

7 days

QPTR 3.2.4 COMANCHE PEAK - UNITS 1 AND 2 3.2-18 Amendment No. 64 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)

LCO 3.2.4 The QPTR shall be 1.02.

APPLICABILITY:

MODE 1 with THERMAL POWER > 50% RTP ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

, 144 A.

QPTR not within limit.

A.1 Reduce THERMAL POWER 3% from RTP for each 1% of QPTR

> 1.00.

AND A.2 Determine QPTR.

AND A.3

NOTE-------------

For Unit 1, Cycle 13, Action A.3 requires SR 3.2.1.1.1, SR 3.2.1.1.2, and SR 3.2.2.1 to be performed.

Perform SR 3.2.1.2.1, SR 3.2.1.2.2 and SR 3.2.2.1.

AND 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after each QPTR determination Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 24 hours after achieving equilibrium conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter (continued)

QPTR 3.2.4 ACTIONS (continued COMANCHE PEAK - UNITS 1 AND 2 3.2-19 Amendment No. 66, 144 CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.4 Reevaluate safety analyses and confirm results remain valid for duration of operation under this condition.

AND A.5

NOTES-------------

1. Perform Required Action A.5 only after Required Action A.4 is completed.

2. Required action A.6 shall be completed whenever Required Action A.5 is performed.

Normalize excore detectors to restore QPTR to within limit.

AND Prior to increasing THERMAL POWER above the limit of Required Action A.1 Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued)

QPTR 3.2.4 ACTIONS (continued COMANCHE PEAK - UNITS 1 AND 2 3.2-20 Amendment No. 64 CONDITION REQUIRED ACTION COMPLETION TIME

, 144 A.

(continued)

A.6

NOTE-------------

1. Perform Required Action A.6 only after Required Action A.5 is completed.

2. For Unit 1, Cycle 13, Action A.6 requires SR 3.2.1.1.1, SR 3.2.1.1.2, and SR 3.2.2.1 to be performed.

Perform SR 3.2.1.2.1, SR 3.2.1.2.2 and SR 3.2.2.1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions at RTP not to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER above the limit of Required Actions A.1 B.

Required Action and associated Completion Time not met.

B.1 Reduce THERMAL POWER to 50% RTP.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

QPTR 3.2.4 COMANCHE PEAK - UNITS 1 AND 2 3.2-21 Amendment 64 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1

NOTES------------------------------------

1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER 75% RTP, the remaining three power range channels can be used for calculating QPTR.

2. SR 3.2.4.2 may be performed in lieu of this Surveillance.

Verify QPTR is within limit by calculation.

7 days SR 3.2.4.2

NOTE--------------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER > 75% RTP.

Verify QPTR is within limit using the core power distribution measurement information.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

, 144

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.3-10 Amendment No. 64 SURVEILLANCE FREQUENCY SR 3.3.1.2

NOTE---------------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is 15% RTP.

Compare results of calorimetric heat balance calculation to NIS Power Range channel and N-16 Power Monitor channel outputs. Adjust NIS Power Range channel outputs if calorimetric heat balance calculation exceeds NIS Power Range channel outputs by more than +2%

RTP. Adjust N-16 Power Monitor channel outputs if calorimetric heat balance calculation exceeds N-16 Power Monitor channel outputs by more than +2% RTP.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.3

NOTE---------------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is t 50% RTP.

Compare results of the core power distribution measurements to Nuclear Instrumentation System (NIS) AFD. Adjust NIS channel if absolute difference is >

3%.

31 effective full power days (EFPD)

SR 3.3.1.4

NOTE----------------------------------

This Surveillance must be performed on the reactor trip bypass breaker for the local manual shunt trip only prior to placing the bypass breaker in service.

Perform TADOT.

62 days on a STAGGERED TEST BASIS (continued)

, 114, 133, 144

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.3-11 Amendment No. 66 SURVEILLANCE FREQUENCY SR 3.3.1.5 Perform ACTUATION LOGIC TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.1.6

NOTE-------------------------------------

Not required to be performed until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after achieving equilibrium conditions with THERMAL POWER 75% RTP.

Calibrate excore channels to agree with core power distribution measurements.

92 EFPD SR 3.3.1.7

NOTES----------------------------------

1. Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3.

2. Source range instrumentation shall include verification that interlocks P-6 and P-10 are in their required state for existing unit conditions.

Perform COT.

184 days (continued

, 114, 144

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0-33 Amendment No. 119, 123, 144 5.6.5 Core Operating Limits Report (COLR) (continued) allowing use of 100.6 percent of rated power in safety analysis methodology when the LEFM¥ is used for feedwater flow measurement.

The approved analytical methods are described in the following documents:

1)

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (W Proprietary)

2)

WCAP-10216-P-A, Revision 1A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION," February 1994 (W Proprietary).

3)

RXE-90-006-P-A, "Power Distribution Control Analysis and Overtemperature N-16 and Overpower N-16 Trip Setpoint Methodology," June 1994.

4)

RXE-88-102-P-A, "TUE-1 Departure from Nucleate Boiling Correlation," July 1992.

5)

RXE-88-102-P, Sup. 1, "TUE-1 DNB Correlation - Supplement 1,"

December 1990.

6)

RXE-89-002-A, "VIPRE-01 Core Thermal-Hydraulic Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications," September 1993.

7)

RXE-91-001-A, "Transient Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications," October 1993.

8)

RXE-91-002-A, "Reactivity Anomaly Events Methodology,"

October 1993.

9)

ERX-2000-002-P, "Revised Large Break Loss of Coolant Accident Analysis Methodology," March 2000.

10)

TXX-88306, "Steam Generator Tube Rupture Analysis,"

March 15, 1988.

11)

RXE-91-005-A, "Methodology for Reactor Core Response to Steamline Break Events," February 1994.

12)

RXE-94-001-A, Safety Analysis of Postulated Inadvertent Boron Dilution Event in Modes 3, 4, and 5, February 1994.

(continued)

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0-34 Amendment No. 119 5.6.5 Core Operating Limits Report (COLR) (continued)

13)

RXE-95-001-P-A, Small Break Loss of Coolant Accident Analysis Methodology, September 1996.

14)

Caldon, Inc. Engineering Report-80P, Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power level Using the LEFM¥ System, Revision 0, March 1997 and Caldon Engineering Report - 160P, Supplement to Topical Report ER-80P; Basis for a Power Uprate With the LEFM¥tm System, Revision 0, May 2000.

15)

ERX-2001-005-P, ZIRLO' Cladding and Boron Coating Models for TXU Electrics Loss of Coolant Accident Analysis Methodologies, October 2001.

16)

WCAP-10444-P-A, Reference Core Report VANTAGE 5 Fuel Assembly, September 1985.

17)

WCAP-15025-P-A, Modified WRB-2 Correlation, WRB-2M, for Predicting Critical Heat Flux in 17x17 Rod Bundles for Modified LPD Mixing Vane Grids, April 1999.

18)

WCAP-13060-P-A, Westinghouse Fuel Assembly Reconstitution Evaluation Methodology, July, 1993.

19)

ERX-04-004-A; Replacement Steam Generator Supplement To TXU Powers Large and Small Break Loss Of Coolant Accident Analysis Methodologies Revision 0, March 2007.

20)

ERX-04-005-A; Application of TXU Powers Non-LOCA Transient Analysis Methodologies to a Feed Ring Steam Generator Design Revision 0, March 2007.

21)

WCAP-11397-P-A, Revised Thermal Design Procedure, April 1989.

22)

WCAP-8745-P-A, Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Functions, September 1986.

23)

WCAP-14565-P-A, VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis, October 1999.

(continued)

, 123, 135, 144

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0-35 Amendment No. 119 5.6.5 Core Operating Limits Report (COLR) (continued)

24)

WCAP-14882-P-A, RETRAN-02 Modeling and Qualification for Westinghouse Pressurized Water Reactor Non-LOCA Safety Analyses, April 1999.

25)

WCAP-10054-P-A, Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code, August 1985.

26)

WCAP-10054-P-A, Addendum 2, Revision 1, Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model, July 1997.

27)

WCAP-10079-P-A, NOTRUMP, A Nodal Transient Small Break and General Network Code, August 1985.

28)

WCAP-16009-P-A, Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), January 2005.

29)

WCAP-12472-P-A, BEACON Core Monitoring and Operations Support System, August 1994.

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

, 123, 135, 144

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0-36 Amendment No. 81 5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a.

RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

1.

Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits, and 2.

Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System.

b.

The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

x WCAP-14040-NP-A; Methodology used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves.

c.

The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

(continued)

, 132, 144

Programs and Manuals 5.6 5.6 Reporting Requirements (continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0-37 Amendment No. 10 5.6.7 Not used 5.6.8 PAM Report When a report is required by the required actions of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.9 Unit 1 Model D76 and Unit 2 Model D5 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.9.2, Steam Generator (SG) Program. The report shall include:

a.

The scope of inspections performed on each SG,

b.

Active degradation mechanisms found,

c.

Nondestructive examination techniques utilized for each degradation mechanism,

d.

Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e.

Number of tubes plugged during the inspection outage for each active degradation mechanism,

f.

Total number and percentage of tubes plugged to date, and

g.

The results of condition monitoring, including the results of tube pulls and in-situ testing, (continued) 3, 128, 144

Programs and Manuals 5.6 5.6 Reporting Requirements (continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0-38 Amendment No. 70 5.6.10 Unit 1 Model D4 Steam Generator Tube Inspection Report

a.

Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged, repaired or designated as an F* tube in each steam generator shall be reported to the Commission;

b.

The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a report within 12 months following the completion of the inspection. This report shall include:

1)

Number and extent of tubes and (for Unit 1 only) sleeves inspected,

2)

Location and percent of wall-thickness penetration for each indication of an imperfection, and

3)

Identification of tubes plugged or repaired.

c.

Results of steam generator tube inspections which fall into Category C-3 shall be reported to the Commission in a report within 30 days and prior to resumption of plant operation. This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

(continued)

, 128, 144

Programs and Manuals 5.6 5.6 Reporting Requirements (continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0-39 Amendment 128 5.6.10 Unit 1 Model D4 Steam Generator Tube Inspection Report (continued)

d.

For implementation of the voltage based repair criteria to tube support plate intersections, notify the staff prior to returning the steam generators to service should any of the following conditions arise:

1.

If estimated leakage based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds the leakage limit (determined from the licensing basis dose calculation for the postulated main steam line break) for the next operating cycle.

2.

If circumferential crack-like indications are detected at the tube support plate intersections.

3.

If indications are identified that extend beyond the confines of the tube support plate.

4.

If indications are identified at the tube support plate elevations that are attributable to primary water stress corrosion cracking.

5.

If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actual measured end-of-cycle) voltage distribution exceeds 1 x 10 -2, notify the NRC and provide an assessment of the safety significance of the occurrence.

, 144

COMANCHE PEAK - UNITS 1 AND 2 5.0-40 Amendment No. 64, 144 High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation:

a.

Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b.

Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

(continued)

High Radiation Area 5.7 5.7 High Area Radiation Area COMANCHE PEAK - UNITS 1 AND 2 5.0-41 Amendment No. 64, 144 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

d.

Each individual or group entering such an area shall possess:

1.

A radiation monitoring device that continuously displays radiation dose rates in the area; or

2.

A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

3.

A radiation monitoring device that continuously, transmits dose rate information and cumulative dose to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure with the area, or

4.

A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii)

Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e.

Except for individuals qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.

(continued)

High Radiation Area 5.7 5.7 High Area Radiation Area (continue)

COMANCHE PEAK - UNITS 1 AND 2 5.0-42 Amendment No. 64, 144 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at I Meter from the Radiation Source or from any Surface Penetrated by the Radiation:

a.

Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1.

All such door and gate keys shall be maintained under the administrative control of the [shift manager], or his or her designee.

2.

Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b.

Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

(continued)

High Radiation Area 5.7 5.7 High Area Radiation Area COMANCHE PEAK - UNITS 1 AND 2 5.0-43 Amendment No. 64, 144 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from theRadiation Source or from any Surface Penetrated by the Radiation: (continued)

d.

Each individual or group entering such an area shall possess:

1.

A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

2.

A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or

3.

A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii)

Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4.

In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

(continued)

High Radiation Area 5.7 5.7 High Area Radiation Area COMANCHE PEAK - UNITS 1 AND 2 5.0-44 Amendment No. 64, 144 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from theRadiation Source or from any Surface Penetrated by the Radiation: (continued)

e.

Except for individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.

f.

Such individual areas that are within a larger area, such as PWR containment, where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

v t e Letter Sequence Other
TAC:MD5243, (Approved, Closed) TAC:MD5244, (Approved, Closed) TAC:MD6212, (Approved, Closed) TAC:MD6213, (Approved, Closed)
Initiation Acceptance... Supplement, Supplement, Supplement, Supplement Administration Questions 2 November 2007 4 February 2008 Answers Results Approval Other: ML080510083
MONTHYEAR2008-01-30 [Table View]

ML080510083

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